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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Fusion Science and Technology
Latest News
DOE issues RFI for a spent fuel consolidated interim storage facility
The Department of Energy’s Office of Nuclear Energy has issued a request for information opportunity for the design and construction of a federal consolidated interim storage facility (CISF) for spent nuclear fuel. The DOE is planning on establishing a federal CISF to manage SNF until a permanent repository is available. In May, the DOE received initial approval, known as “Critical Decision-0,” for such a facility.
The deadline for submissions is September 5.
K. Hoshino, T. Yamamoto, H. Tamai, K. Ohasa, H. Kawashima, Y. Miura, T. Ogawa, T. Shoji, T. Shibata, K. Kikuchi, M. Sawahata, K. Takahashi
Fusion Science and Technology | Volume 49 | Number 2 | February 2006 | Pages 139-167
Technical Paper | JFT-2M Tokamak | doi.org/10.13182/FST06-A1092
Articles are hosted by Taylor and Francis Online.
We briefly present the experimental results obtained using the various heating and current drive systems, such as electron cyclotron heating, fast wave, lower hybrid wave, ion cyclotron range of frequency, neutral beam injection heating, or the external coil systems or the divertor bias system developed in JFT-2M from the viewpoint of the active control of the tokamak plasma. The features and design concepts of each system are described briefly, as we had to develop such systems to carry out the physical research. The experimental findings in plasma heating, current drive, and advanced plasma control in the JFT-2M tokamak contributed to the design and experiments in the larger tokamaks and to ITER.